公开(公告)号：US20070219402A1

公开(公告)日：2007-09-20

申请号：US10599897

申请日：2005-04-13

Applicant: Ian Godfrey ,  Edward Butcher ,  Joanne Parr

Inventor： Ian Godfrey ,  Edward Butcher ,  Joanne Parr

IPC: G21F9/28

CPC classification number: G21F9/304 ,  G21F1/042 ,  G21F9/28 ,  G21F9/34 ,  G21F9/36

Abstract: The invention provides a method for the encapsulation of uranium metal which comprises treating the metal with an encapsulant which comprises a cementitious material and curing the cementitious material, the process additionally comprising the provision of means for the minimisation of the corrosion of the metal. Suitable modes for the provision of means for the minimisation of corrosion include the provision of a source of oxygen within the cement matrix, either by facilitating enhanced oxygen access from the atmosphere using air entraining agents or cenospheres or by the inclusion of an independent source of oxygen, for example a peroxide. An alternative mode for the provision of means for the minimisation of corrosion comprises facilitating the minimisation of the water content of the matrix, which is conveniently achieved by the addition of superplasticisers. The method allows for the long team storage of uranium metal and provides significant benefits in terms of health, safety and the environment.

Abstract translation: 本发明提供了一种用于包封铀金属的方法，其包括用包含水泥质材料和固化水泥材料的密封剂处理金属，该方法还包括提供用于最小化金属腐蚀的装置。 提供用于最小化腐蚀的手段的合适方式包括：在水泥基体内提供氧源，方法是利用加气剂或空心微球从气氛中增强氧气的通入，或者通过加入独立的氧气源 ，例如过氧化物。 提供用于最小化腐蚀的装置的替代方式包括促进基质的含水量的最小化，这通过添加超增塑剂而方便地实现。 该方法允许长期存储铀金属，并在健康，安全和环境方面提供显着的益处。

公开(公告)号：US20060211908A1

公开(公告)日：2006-09-21

申请号：US11364643

申请日：2006-02-28

Applicant: Weiliang Gong ,  Werner Lutze ,  Ian Pegg

Inventor： Weiliang Gong ,  Werner Lutze ,  Ian Pegg

IPC: G21F9/00 ,  G21F9/16

CPC classification number: G21F9/304 ,  C04B28/006 ,  C04B28/008 ,  C04B28/08 ,  G21F9/16 ,  Y02P40/165 ,  Y02W30/91 ,  Y02W30/92 ,  Y02W30/94 ,  C04B18/0463 ,  C04B18/08 ,  C04B22/062 ,  C04B14/106 ,  C04B18/146

Abstract: Treatment of a radioactive waste stream is provided by adding sodium hydroxide (NaOH) and/or potassium hydroxide (KOH) together with a rapidly dissolving form of silica, e.g., fumed silica or fly ash. Alternatively, the fumed silica can be first dissolved in a NaOH/KOH solution, which is then combined with the waste solution. Adding a binder that can be a mixture of metakaolin (Al2O3.2SiO2), ground blast furnace slag, fly ash, or other additives. Adding an “enhancer” that can be composed of a group of additives that are used to further enhance the immobilization of heavy metals and key radionuclides such as 99Tc and 129I. An additional step can involve simple mixing of the binder with the activator and enhancer, which can occur in the final waste form container, or in a mixing vessel prior to pumping into the final waste form container, depending on the particular application.

Abstract translation: 通过将氢氧化钠（NaOH）和/或氢氧化钾（KOH）与快速溶解形式的二氧化硅（例如热解法二氧化硅或飞灰）一起加入来提供放射性废物流的处理。 或者，可以将热解法二氧化硅溶解在NaOH / KOH溶液中，然后将其与废溶液组合。 加入可以是偏高岭土（Al 2 O 3 O 3·2SSi 2/2）的混合物的粘合剂，高炉炉渣，粉煤灰或 其他添加剂。 添加可以由一组添加剂组成的“增强剂”，其用于进一步增强重金属和关键放射性核素如99和99 I的固定化。 根据具体应用，另外的步骤可以包括将粘合剂与活化剂和增强剂简单混合，活化剂和增强剂可以在最终废物形式的容器中发生，或者在泵入最终废物形式的容器之前在混合容器中。

公开(公告)号：US5100586A

公开(公告)日：1992-03-31

申请号：US556086

申请日：1990-07-20

Applicant: Hamlin M. Jennings ,  Simon K. Hodson

Inventor： Hamlin M. Jennings ,  Simon K. Hodson

IPC: G21F9/30 ,  G21F9/34

CPC classification number: G21F9/34 ,  G21F9/304

Abstract: Novel cementitious containers for storage of hazardous waste are disclosed having an inner layer of substantially unhydrated cement in contact with the hazardous waste and an outer layer of hydrated cement. Cementitious hazardous waste containers may be prepared by compressing powdered hydraulic cement around solid hazardous waste materials and then hydrating an outer layer of the powdered hydraulic cement. An inner layer of powdered hydraulic cement remains unhydrated and capable of reacting with any water which might breach the outer layer or originate with the hazardous waste itself. The inner layer of powdered hydraulic cement is also capable of reacting with any carbon dioxide or carbon monoxide generated by decomposition of organic waste materials.

Abstract translation: 公开了用于存储危险废物的新型水泥容器，其具有与危险废物接触的基本上未水合的水泥的内层和水合水泥的外层。 水泥危险废物容器可以通过在固体危险废物周围压缩粉末水硬性水泥，然后水化粉末水硬性水泥的外层来制备。 粉末水硬性水泥的内层保持未水合，并且能够与可能破坏外层或源自危险废物本身的任何水反应。 粉状水硬性水泥的内层也能够与有机废料分解产生的二氧化碳或一氧化碳反应。

公开(公告)号：US4540512A

公开(公告)日：1985-09-10

申请号：US482737

申请日：1983-04-06

Applicant: Edward J. Lahoda

Inventor： Edward J. Lahoda

IPC: C01B35/10 ,  C03C1/02 ,  G21F9/06 ,  G21F9/08 ,  G21F9/30 ,  G21F9/16

CPC classification number: G21F9/305 ,  G21F9/06 ,  G21F9/08 ,  G21F9/304

Abstract: Disclosed is a process for separating and recovering boric acid from water containing solids which include boric acid and radionuclides. In the first step, the water is separated from the solids by evaporation of the water at a temperature under 130.degree. F. In the second step, an alcohol selected from the group consisting of methanol, ethanol, propanol, isopropanol, and mixtures thereof is added to the remaining solids in the amount of at least 1.4 times that stoichiometrically required to react with the boric acid to form boron alkoxide and water to about 100 mole % in excess of stoichiometric. In the third step, the boron alkoxide is separated from the remaining solids by evaporation of the boron alkoxide. In the fourth step, water is added to the volatilized boron alkoxide to form boric acid and an alcohol. And finally, the alcohol is separated from the boric acid by evaporating the alcohol.

Abstract translation: 公开了一种从包含硼酸和放射性核素的含固体的水中分离和回收硼酸的方法。 在第一步骤中，通过在130°F的温度下蒸发水分将水与固体分离。在第二步中，选自甲醇，乙醇，丙醇，异丙醇及其混合物的醇是 以与硼酸反应形成硼醇盐和水至少超过化学计量的约100摩尔％的化学计量所需的至少1.4倍的量加入到剩余的固体中。 在第三步中，通过蒸发硼醇盐将硼醇盐与剩余的固体分离。 在第四步骤中，向挥发的硼醇盐中加入水以形成硼酸和醇。 最后，通过蒸发酒精将醇与硼酸分离。

公开(公告)号：US4483789A

公开(公告)日：1984-11-20

申请号：US513953

申请日：1983-07-15

Applicant: Siegmar Kunze ,  Gerhard Eden ,  Rainer Koster

Inventor： Siegmar Kunze ,  Gerhard Eden ,  Rainer Koster

IPC: G21F9/00 ,  G21F9/16 ,  G21F9/30

CPC classification number: G21F9/165 ,  G21F9/304

Abstract: A method for forming a hardened product containing a radioactive ion exchanger resin in a condition for permanent, noncontaminating storage, by the steps of:providing, before fixing, a mass of such ion exchanger resin saturated in water, the resin being at least one resin selected from the group consisting of spherical resins and powdered resins;mixing the resin mass, with stirring, with a blast furnace cement having a composition which causes it to exhibit slow initial hardening, high sulfate resistance and low hydration heat and with a quantity of additional water equal in weight to 20% to 40% of the weight of the blast furnace cement; andallowing the resulting mixture to harden at room temperature.

Abstract translation: 一种在永久性，不污染储存条件下形成含有放射性离子交换树脂的硬化物的方法，其特征在于，在固定前提供一定量的这种在水中饱和的离子交换树脂，所述树脂为至少一种树脂 选自球形树脂和粉末状树脂; 在搅拌下将树脂块与具有使其呈现缓慢的初始硬化，高耐硫酸盐性和低水合热的组成的高炉水泥混合，并且一定量的另外的水的重量相当于其重量的20％至40％ 高炉水泥重量; 并使所得混合物在室温下硬化。

公开(公告)号：US4139488A

公开(公告)日：1979-02-13

申请号：US698750

申请日：1976-06-22

Applicant: Karl Knotik ,  Peter Leichter ,  Heinz Jakusch

Inventor： Karl Knotik ,  Peter Leichter ,  Heinz Jakusch

IPC: G21F9/36 ,  B09B5/00 ,  G21F9/00 ,  G21F9/30 ,  G21F9/34

CPC classification number: G21F9/307 ,  G21F9/008 ,  G21F9/302 ,  G21F9/304

Abstract: Solid radioactive or toxic wastes are prepared for long-term storage by adding a hardenable binding agent to a container filled with the waste under a partial vacuum. The improved homogeneity of mixing of the binder and waste is enhanced by removing the partial vacuum prior to the hardening of the binder. The temperature of the container is maintained, during the addition of the binder agent to the waste, at a temperature at least equal to the melting temperature of the binder to assure thorough impregnation of the waste thereby. Preferably, the container supporting the resultant waste-binder matrix is placed in a larger container, and the space between the two containers is filled with bituminous material or concrete to provide added security against water penetration during storage.

Abstract translation: 通过在部分真空下向填充有废物的容器中加入可硬化粘合剂，可以制备固体放射性或有毒废物进行长期储存。 通过在粘合剂硬化之前去除部分真空来提高粘合剂和废料混合的均匀性。 在粘合剂添加到废物中时，在至少等于粘合剂的熔融温度的温度下保持容器的温度，以确保废物的充分浸渍。 优选地，将所得到的废物 - 粘合剂基质的容器放置在更大的容器中，并且两个容器之间的空间填充有沥青材料或混凝土，以提供在储存期间防止水渗透的附加安全性。

公开(公告)号：US11978568B1

公开(公告)日：2024-05-07

申请号：US18239313

申请日：2023-08-29

Applicant: The Fourth Research and Design Engineering Institute of China National Nuclear Corporation

Inventor： Yang Gao ,  Juan Sun ,  Yifu An ,  Guoxi Lian ,  Xuyang Wu

IPC: G21F9/30 ,  B09B3/70 ,  B09B101/55 ,  C04B12/00 ,  C04B14/04 ,  C04B111/00

CPC classification number: G21F9/304 ,  B09B3/70 ,  C04B12/00 ,  C04B14/042 ,  B09B2101/55 ,  C04B2111/00767

Abstract: A method for stabilizing a neutralization slag of uranium associated zirconium and zirconia, and a stabilization agent used therein are disclosed. The stabilization agent includes the following components in parts by weight: a pretreatment agent of 2-8 parts, anhydrous calcium chloride of 2-6 parts, an adsorbent of 3-5 parts and a stabilizer of 4-9 parts. The stabilization agent is used to stabilize the uranium that is existed in the neutralization slag in a waste slag. The method includes the following steps: the pretreatment agent is used to alkalize and disperse the neutralization slag; soluble calcium salt is added to cement the neutralization slag; and the adsorbent and the stabilizer are used as a composite material to passivate the neutralization slag. The method has low cost, fast effectiveness, simple process, easy operation, and long-term stable remediation efficiency, which can be applied to the treatment and disposal of associated radioactive waste residues.

公开(公告)号：US20240105353A1

公开(公告)日：2024-03-28

申请号：US18476708

申请日：2023-09-28

Applicant: Deep Isolation, Inc.

Inventor： Richard A. Muller

IPC: G21F9/34 ,  B65D88/76 ,  G21F9/30

CPC classification number: G21F9/34 ,  B65D88/76 ,  G21F9/304

Abstract: A hazardous material storage repository includes a borehole that extends into the Earth from a terranean surface. The borehole includes an entry and a hazardous material storage borehole portion formed in a subterranean salt formation. The repository includes a storage canister positioned in the hazardous material storage borehole portion. The storage canister is sized to fit from the entry through a substantially vertical borehole portion of the borehole, and into the hazardous material storage borehole portion. The storage canister includes an inner cavity sized to enclose nuclear waste material that includes TRansUranic waste.

公开(公告)号：US20160141059A1

公开(公告)日：2016-05-19

申请号：US14897930

申请日：2014-06-12

Applicant: GRANIT TECHNOLOGIES S.A.

Inventor： Boris CORREA ,  Olivier MERCIER

IPC: G21F9/30

CPC classification number: G21F9/30 ,  B01D1/0047 ,  C02F1/04 ,  C02F1/66 ,  C02F11/008 ,  C02F11/08 ,  C02F2101/006 ,  G21F9/08 ,  G21F9/165 ,  G21F9/304

Abstract: A method and plant for wet-route oxidation treatment of hazardous organic waste products, notably radioactive wastes, which may contain mineral fillers, the waste products being treated in a secure environment. The plant comprises a closed space, with a mechanism for bringing a volume of hazardous organic waste products containing mineral fillers, adding a given quantity of water mixed with a base to the predetermined volume in order to adjust the pH to a determined value so as to make a solution and/or a liquid suspension, with a pressure reactor and with mechanism for transferring the solution and/or liquid suspension into the pressure reactor, and a device for introducing an oxygen atmosphere into the pressure reactor and for pressurizing the atmosphere. A heating mechanism is provided for subjecting the contents of the pressure reactor to heat treatment at a temperature between 150 and 350° C. to complete the wet-route oxidation.

Abstract translation: 用于湿路线氧化处理有害有机废物的方法和设备，特别是可能含有矿物填料的放射性废物，废物在安全的环境中进行处理。 该植物包括封闭空间，其具有用于使大量含有矿物填料的有害有机废物产生的机构，将一定量的与基料混合的水添加至预定体积，以便将pH调节至确定值，以便 用压力反应器和用于将溶液和/或液体悬浮液转移到压力反应器中的机构制备溶液和/或液体悬浮液，以及用于将氧气氛引入压力反应器并对气氛加压的装置。 提供一种加热机构，用于使压力反应器的内容物在150-350℃的温度下进行热处理，以完成湿路径氧化。

公开(公告)号：US20140336437A1

公开(公告)日：2014-11-13

申请号：US14360549

申请日：2011-11-25

Applicant: Ying Zhao ,  Laixi Huang ,  Yucai Ye ,  Ge Gao ,  Yongdong Ye ,  Caiyuan Deng ,  Zhigang Zhang ,  Jianchun Yuan

Inventor： Ying Zhao ,  Laixi Huang ,  Yucai Ye ,  Ge Gao ,  Yongdong Ye ,  Caiyuan Deng ,  Zhigang Zhang ,  Jianchun Yuan

IPC: G21F9/30 ,  C04B7/34 ,  C04B24/26

CPC classification number: G21F9/304 ,  B09B3/0025 ,  B09B3/0041 ,  C04B7/34 ,  C04B24/26 ,  C04B24/2641 ,  C04B28/02 ,  C04B2111/00767 ,  G21F9/165 ,  Y02W30/91 ,  C04B12/04 ,  C04B18/0463 ,  C04B22/0093 ,  C04B22/062 ,  C04B22/10 ,  C04B24/2647

Abstract: A cement curing formulation and curing method for high-level radioactive boron waste resins from a nuclear reactor. The curing formulation comprises the following raw materials: cement, lime, water, curing aids and additives. The curing method comprises: (1) weighing the raw materials and the high-level radioactive boron waste resins, and adding lime into a curing container; (2) then adding the high-level radioactive boron waste resins; (3) feeding other raw materials under stirring; (4) adding the cement and supplementing water depending on the moisture state of the cement, and stirring until uniform; and (5) standing and maintaining after stirring until uniform. The curing formulation has the features of a high curing containment rate, high strength of the cured body, better water resistance, better freeze-thaw resistance, and low radioactive leakage.

Abstract translation: 来自核反应堆的高级放射性硼废树脂的水泥固化配方和固化方法。 固化配方包括以下原料：水泥，石灰，水，固化助剂和添加剂。 固化方法包括：（1）称量原料和高放射性硼废树脂，并在固化容器中加入石灰; （2）加入高放射性硼废树脂; （3）搅拌喂养其他原料; （4）根据水泥的水分状况加水泥和补水，搅拌至均匀; 和（5）搅拌后立即保持均匀。 固化剂具有固化速度快，固化体强度高，耐水性好，抗冻融性好，放射性低的特点。